ML25197A093
| ML25197A093 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 01/14/1974 |
| From: | Stratton W US Atomic Energy Commission (AEC) |
| To: | Ray D US Atomic Energy Commission (AEC) |
| References | |
| Download: ML25197A093 (1) | |
Text
ADVISORY COMMITTEE ON REACTOR SAFEGUARDS UNITED STATES ATOMIC ENERGY COMMISSION WASHINGTON, O.C. 2.0545 Januarv 14, 1974 Honorable Dix.t Lee Ray Chainnan
- u. s. Atomic Energy Corrmission Washington, D. c.
20545
Subject:
REPOm' Q.~ THE EDWIN I. HAID! :t-.i1.JCLE.AR PIA"Il', U-1IT l
Dear Dr. Ray:
During its 165th meeting, January 10-12, 1974, the.Advisory Corrmittee on Reactor Safeguards canpleted its revieH of t."1e application by the Georgia Pa,.;rer Company for authorization to operate the Ed.vlL'l I. Hatch Huclear Plant, Unit 1. A Subcarnnittee rrade a tour of the partially CCJrr?leted plant on February 27, 1973.
'Ihe project was consid.ered during Subccmnittee meetings in Washington, D. c., on t~y 24, 1973, m-.d Dcr-....3:'.bc.....r 20, 1973, and at the Canmittee's 158th TileE:!ting, June 7-9, 1973, in tiashington, D. c. During its review, the Corrmittee had the benefit of discussions with representatives and consultants of the C--eorgia PC1.-1er Company, Southern Services Incoq:orated, the C--eneral Electric Company, and the AEC Fegulatory Staff. The Cor:mittee also had the be..."'lefit of t..'-ie documents listed. The Corrrnittee forwarded an interim report on the operation of this unit to the Corrrnission on June 12, 1973.
F..atc..'1, Unit 1, utilizes a General Electric boiling water reactor si.inilar to those provided for Brunswick Units 1 and 2 and for the Cooper Nuclear Station previously reviewed b-y the.A.CRS for operation.
T'ne Hatch reactor is designed to prcx:1uce 2436 r-i,1t.
'Ihe applicant, with the General Electric Corrpa::1y, has studied the problem of fu~l densification. The analyses indicate tii.at, except in regard to pea"-< clad temperatures in postulated loss of coolant accidents, the effects of e:-(1::iected densification are relativ~ly srrall.
'lb assure confomance wit.'li. ~_ak cl.ad teffi.?erature and ot.'lrer li."'1its of the Interi...-n Acceptance Criteria, the applicant pro:;::oses to operate the F.atch reactor in such rt'anner as to rraintain the rnaxiraum average planar 1iJ1ear heat generation rate t,w>LHGR) at all times belCM a specific alla.'able value. So-called "gai-rrra" c-urves, developed by the apolicant 740
Hor.arable Dixy Lee 3-ay 2 -
Jnnu:rrv 14, 1974 and revia-;ed and approved. (to date, only for the first fuel cycle) by b."le 7,egulatory Staff, depict the allowable value as o. famction of fuel exposure. The Corrrni ttee believes that the approach described is acceptable.
P.J:1,1ev,=,.....r, the ACRS r~.s that t..~e !?.egulatory Staff assure itself that the detailed proceo.ures to be e-nplo:::ted by t.1-ie re-actor operator to acca:T'f)lish and to de."'X:lnstrate compliance with the pro;osed lit-nits on core conditions are adequate. Particular a:ip,.1lasis should be given to the procedure to be folla,-1ed \\vnen the <:Xr-:'lpUter no:rmally used for core p:,wer distribution calculation is inoperable or unavailable. T'ne Ccrnni ttee vtlshes to be kept L'1fo:rrned.
Re-evaluation of core o~ating l:L"'!'i.ts will be necessary as a result of the recently pranulgated.F>..cc-9ptance Criteria for E:I:tt.ergency Core Cooling Systems.
~11e Coranittee \\*tlshes to be kept in£omErl.
Sir..ce b1/2e Ccrm>ittee's last report, the a:9?licant has nade fu..rt.'-1.er progress in arrange-re."1.ts for emerga'lCY procedures to be followed in case of an accidental release of radioactive rraterials fran b.'1e pla.--it.
Yet to be confirmed, however, are plans of the state agencies whose actions would be essential in dealing with the po_oulation in case of such an event.
The Comni. ttee recorarends that the ap-olicant and the AOC staff continue to collaborate with the State in-noving ahead to
~lete develo:i;rnent of an errergenC'J action plan, and t.h:at the adequaC'/
of arrangements for in'?lementing such a plan be confirmed. prior to initial operation of the plant.
The Adviso~.f camri.ttee on Reactor Safeguards believes that, if due regard is given to the items mentioned above and those rrentione::1 in its June 12, 1973 Interim Report, and subject to satisfactory conple-tion of construction and preoperational testing, there is reasonable assurance that the Edwin I. F..a.tch Nuclear Plant, Unit 1 can be operated at p:,wer levels up to 2436 iYHt without undue risk to the health and safety of t..11e public.
References attache::1.
Sincerely yours,
- w. R. Stratton Chail:m3n 741
- t-:onorable Dbo/ lee Ray Januarv 14, 1974 References
- 1. Arnendm,ents 34 through 40 to the License Application
- 2.
Georgia Power Ccrrpany letter aated October 25, 1973, furnishing information on Control Rod Drop Accident and Core T'ne:rnal Pa.*;er Level
- 3. Directorate of Licensing Supplar.ent No. 1 to the Safety Evaluation Refx)rt, dated DecE?Tlber 10, 1973 742